Letter Sequence RAI |
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TAC:M97546, TSTF-2, Revise Battery Surveillance Weekly Frequencies, Add Bases for 3.8.6 Actions Note, Revise DC Sources - Shutdown and Inverters - Shutdown to Address Specific Subsystem Requirements, TSTF-16 (Open) TAC:M97547, TSTF-2, Revise Battery Surveillance Weekly Frequencies, Add Bases for 3.8.6 Actions Note, Revise DC Sources - Shutdown and Inverters - Shutdown to Address Specific Subsystem Requirements, TSTF-16 (Open) TAC:M97548, TSTF-2, Revise Battery Surveillance Weekly Frequencies, Add Bases for 3.8.6 Actions Note, Revise DC Sources - Shutdown and Inverters - Shutdown to Address Specific Subsystem Requirements, TSTF-16 (Open) TAC:M97549, TSTF-2, Revise Battery Surveillance Weekly Frequencies, Add Bases for 3.8.6 Actions Note, Revise DC Sources - Shutdown and Inverters - Shutdown to Address Specific Subsystem Requirements, TSTF-16 (Open) |
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MONTHYEARNUREG-1431, Forwards RAI Re Proposed Amend to TS for Byron & Braidwood Stations,To Be Consistent W/Improved TSs in NUREG-1431, STS-Westinghouse Plants, Rev 1.Requests Response to RAI within 30 Days of Date of Ltr1998-04-29029 April 1998 Forwards RAI Re Proposed Amend to TS for Byron & Braidwood Stations,To Be Consistent W/Improved TSs in NUREG-1431, STS-Westinghouse Plants, Rev 1.Requests Response to RAI within 30 Days of Date of Ltr Project stage: RAI NUREG-1431, Forwards Request for Addl Info Re Amend to TS Sections 5.0 & 3.8,proposed by Util on 961213,per Improved TS in NUREG-14311998-06-12012 June 1998 Forwards Request for Addl Info Re Amend to TS Sections 5.0 & 3.8,proposed by Util on 961213,per Improved TS in NUREG-1431 Project stage: RAI ML20154A1331998-09-29029 September 1998 Forwards Request for Addl Info Re Byron Station,Units 1 & 2 & Braidwood Station,Units 1 & 2.Written & Electronic Responses Requested within 30 Days of Date of Ltr Project stage: RAI ML20198K5771998-12-23023 December 1998 Forwards Revised TS Pages (3/4 3-53,3/4 3-53a,6-27 & 6-27a), for Bs,Units 1 & 2.Revised Pages Provides Early Implementation of Rv LI Sys Requirements.Required Procedure Changes & Training Were Completed Prior to Implementation Project stage: Other 1998-04-29
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station 05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999 Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr ML20210E2151999-07-23023 July 1999 Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999 Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted 1999-09-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) IR 05000456/19993011999-07-15015 July 1999 Forwards Operator Licensing Exam Repts 50-456/99-301OL & 50-457/99-301OL for Test Administered from 990607-11 to Applicants for Operating Licenses.Three Out of Four Applicants Passed Exams ML20209H5141999-07-14014 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle ML20196K0161999-06-30030 June 1999 Discusses 990622 Meeting at Byron Nuclear Power Station in Byron,Il.Purpose of Visit Was to Meet with PRA Staff to Discuss Ceco Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff ML20196H0631999-06-28028 June 1999 Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D4591999-06-18018 June 1999 Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20196A6671999-06-17017 June 1999 Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff ML20195J3741999-06-14014 June 1999 Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative ML20195F3231999-06-0909 June 1999 Informs That in ,Arrangements Finalized for Exam to Be Administered at Plant During Wk of 990607.All Parts of Plant Initial Licensed Operator Exam Approved for Administration ML20207G0601999-06-0707 June 1999 Provides Updated Info Re Number of Failures Associated with Initial Operator License Exam Administered from 980914-0918. NRC Will Review Progress Wrt Corrective Actions During Future Insps ML20207G0421999-06-0404 June 1999 Forwards Insp Repts 50-454/99-04 & 50-455/99-04 on 990330-0510.Violations Identified & Being Treated as non-cited Violations ML20207E5451999-05-28028 May 1999 Forwards Insp Repts 50-454/99-07 & 50-455/99-07 on 990517-20.No Violations Noted.Fire Protection Program Was Effective ML20207B6361999-05-25025 May 1999 Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20206U3471999-05-20020 May 1999 Forwards Insp Rept 50-454/99-05 on 990401-22.No Violations Noted.Insp Reviewed Activities Associated with ISI Efforts Including Selective Exam of SG Maint & Exam Records, Calculations,Observation of Exam Performance & Interviews ML20207A5891999-05-20020 May 1999 Forwards Insp Repts 50-456/99-05 & 50-457/99-05 on 990405-23.Two non-cited Violations Identified ML20207A2151999-05-19019 May 1999 Forwards Insp Repts 50-454/99-06 & 50-455/99-06 on 990419-23.No Violations Noted.Insp Consisted of Review of Liquid & Gaseous Effluent Program,Radiological Environmental Monitoring Program,Auditing Program & Outage Activities ML20206U4641999-05-18018 May 1999 Responds to Util 990517 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3.0.3. Documents 990516 Telcon with Licensee Re NOED ML20207B8751999-05-18018 May 1999 Responds to Ltr Dtd 990225,expressing Concerns That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazards at Some Commercial Nuclear Power Plants in Us ML20206N4791999-05-13013 May 1999 Forwards RAI Re 980529 Amend Request for Byron & Braidwood to Credit Automatic PORV Operation for Mitigation of Inadvertent SI at Power Accident.Response Requested 60 Days After Receipt Date ML20206Q5321999-05-11011 May 1999 Forwards Insp Repts 50-456/99-06 & 50-457/99-06 on 990302-0413.Configuration Control Error Resulted in Isolation of Unit 1 Emergency Boration Flow Path Through Designated Boric Acid Pump for Period of 3 H Occurred ML20206H8161999-05-0505 May 1999 Confirms Discussion Re Meeting to Be Conducted on 990527 at Braidwood Station Training Building.Meeting Will Discuss Braidwood Station Performance as Described in Most Recent Plant Performance Review 1999-09-08
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l April 29, 1998 Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company I Executive Towers West lli.
1400 Opus Place, Suite 500 Downers Grove, IL 60515
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 (TAC NOS. M97548, j M97549, M97546 AND M97547).
1
Dear Mr. Kingsley:
l On December 13,1996, Commonwealth Edison Company (Comed) proposed to amend the technical specifications (TS) for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 .
and 2, to be consistent with the improved TS in NUREG-1431, " Standard Technical !
Specifications - Westinghouse Plants,' Revision 1. During the course of our review, we have identified the need for further information as discussed in the enclosed request for additional information (RAl). This request seeks to clarify Section 3.8.
To support the NRC staff's review schedule, your written and electronic response to this RAI is requested within 30 days of the date of this letter. Should you have any questions, please l contact me at (301) 415-1391.
' Sincerely, ,
ORIG. SIGNED BV:
Ramin R. Assa, Project Manager Project Directorate 111-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, i STN 50-456, STN 50-457
)
Enclosure:
RAI cc w/ encl: see next page !
1
~ DISTRIBUTION: i Docket PUBLIC PDill-2 r/f EAdensam SRichards '
CMoore RAssa JHickman OGC,015818 ACRS, T2E26 piM l
' MJordan, Rlli - SBailey !
DOCUMENT NAME: G:\CMNTJR\ BRAID-BY\BB97548.RAI To receive a copy of this document, indicate in thebox: -C" = Copy w/o encls "E" = Copy w/encls "N"= No copy i OFFICE PM:PD3h 6 W33-2 &D:PD3-2 l4 ,
I NAME RASSA T h &l@$QRE SRICHARDS CfV I DATE 04/19 /98 OT/9 /98 04/ #1 /98 OFFICIAL RECORD COPY
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g 568 %g% UNITED STATES l g j t
NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 2006H001 i s., ...../
April 29,' 1998 Mr. Oliver D. Kingsley, President l Nuclear Generation Group i
Commonwealth Edison Company Executeve Towers West lli 1400 Opus Place, Suite 500 l
Downers Grove, IL 60515
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 (TAC NOS. M97548, M97549, M97546 AND M97547)
Dear Mr. Kingsley:
On Dect mber 13,1996, Commonwealth Edison Company (Comed) proposed to amend the technical specifications (TS) for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, to be consistent with the improved TS in NUREG-1431, " Standard Technical Specifications - Westinghouse Plants," Revision 1. During the course of our review, we have identified the need for further information as discussed in the enclosed request for additional information (RAl). This request seeks to clarify Section 3.8.
I To support the NRC staff's review schedule, your written and electronic response to this RAI is requested within 40 days of the date of this letter. Should you have any questions, please contact me at (301) 415-1391.
Sincerely, m ,
Ramin R. Assa, Project Manager l Project Directorate lll-2 t
Division of Reactor Projects - til/IV Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, l . STN 50-456, STN 50-457
Enclosure:
RAI cc w/oncl: see next page l'
l O. Kingsley . Byron /Braidwood Stations .
Commonwealth Edison Company cc: ,
Ms. C. Sue Hauser, Project Manager George L. Edgar Westinghouse Electric Corporation Morgan, Lewis and Bochius Energy Systems Business Unit 1800 M Street, N.W.~
Post Office Box 355 Washington, DC 20036 Pittsburgh, Pennsylvania 15230 Attomey General Joseph Gallo 500 S. Second Street Gallo & Ross Springfield, Illinois 62701 1250 Eye St., N.W., Suite 302 Washington, DC 20005 lilinois Department of Nuclear Safety Office of Nuclearcacility Safety Michael 1. Miller, Esquire. 1035 Outer Park Drive Sidley and Austin _
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Howard A. Leamer 4450 N. German Church Road Environmentallaw and Policy Byron, Illinois 61010-9794 Center of the Midwest 35 East Wacker Dr., Suite 1300 Commonwealth Edison Company Chicago, Illinois 60601 Site Vice President - Byron 4450 N. German Church Road U.S. Nuclear Regulatory Commission Byron, Illinois 61010-9794 Byron Resident inspectors Office l
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RR 1, Box 79 ,
Regional Administrator, Region ill Braceville, Illinois 60407 U.S. Nuclear Regulatory Commission 801 Warrenville Road Mr. Ron Stephens Lisle, Illinois 60532-4351 lilinois Emergency Services and Disaster Agency Ms. Lorraine Creek 110 E. Adams Street RR 1, Box 182 Springfield, Illinois 62706 Mantono, Illinois 60950 Chairman Chairman, Ogle County Board Will County Board of Supervisors Post Office Box 357 Will County Board Courthouse Oregon, Illinois 61061 Jo:iet, Illinois 60434 Mrs. Phillip B. Johnson Commonwealth Edison Company 1907 Stratford Lane Braidwood Station Manager Rockford, Illinois 61107 RR 1, Box 84 Braceville, Illinois 60407
1
,- O. Kingsley Commonwealth Edison Company - Byron /Braidwood Stations .
Ms. Bridget Little Rorem Ms. Irene Johnson, Licensing Director Appleseed Coordinator - Nuclear Regulatory Services
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Commonwealth Edison Company Braceville,IL 60407 Reg. Assurance Supervisor- Byron 4450 N. German Church Road Mr. David Helwig Byron, Illinois 61010-9794
,- Senior Vice President Commonwealth Edison Company Mr. Michael J. Wallace Executive Towers West I'l Senior Vice President 1400 Opus Place, Suite 900 Commonwealth Edison Company Downers Grove,IL 60515 Exccutive Towers West lli 1400 Opus Place, Suite 900 Mr. Gene H. Stanley Downers Grove, IL 60515 PWR's Vice President Commonwealth Edison Company Executive Towers West til 1400 Oous Place, Suite 900 Downers Grove, IL 60515 Mr. Steys Perry BWR's Vice President Commonwealth Edison Company Executive Towers West lli 1400 Opus Place, Suite 900 Downers Grove, IL 60515
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! Byron & Braidwood Improved TS Review Comments ITS Section 3.8, Electrical Power Systems ITS 3.8.1 -
3.8.1-1 DOC A2
.The discussion in DOC A2 is not consistent with Insert 3.8-2D or with ITS 3.8.1 Condition ;
G. Is the DOC or the LCO and the Insert correct? I 3.8.1-2 JFD BP45 Insert B 3.815A is consistent with the ITS Bases .1iscussion for ITS 3.8.1 Condition G. I However, the inclusion of the two DG inoperable example is not helpful in explaining the l condition because that example does not e.xplain the level of equipment operability at which the Condition must be entered.
3.8.1-3 DOC LA4 The DOC states "This change is required to properly reflect the manufacturer's current recommendation ..." and "the manufacturer is indifferent to the benefits of this type of start" What is the documented basis for these statements?
l 3.8.1-4 DOC L8 The discussion states "... end eliminating an upper voltage criteria ..." What voltage criteria are eliminated?
l 3.8.1-5 DOC M11 1
The CTS markup (CTS 4.8.1.1.2.f.2 ) of the voltage values (-420, + 210) results in values '
that are inconsistent with those in ITS 3.8.1.9.
'l 3.8.1-6 Bases JFD P36 The JFD does not appear to be applicable in the markup of the second paragraph of STS Bases page B 3.8-9.
3.8.1-7 Bases JFD B1 and insert B 3.8-27A (Bases JFD P21)
The markup of the STS Bases for SR 3.8.1.3 eliminates the discussion of power factors (STS B 3.8-13) and substitutes a discussion of DG operation from 0 to 1000 kVars. Use of Bases JFD B1 is not apprcpriate and if Beses JFD B3 was intended, a justification of the O to 1000 kVars range shou'd be provided as it does not appear in the CTS. Likewise, while Bases JFD P21 makes the case for discor,tinuing testing at rated power factor, it fails to provide any technical basis for the guidance provided in Insert B 3.8-27A.
BB2_CR_3.8 1 April 16,1998 ENCLOSURE
I Byron & Braidwood improved TS Review Comments j ITS Section 3.8, Electrical Power Systems 1 3.8.1-8 ITS 3.8.1 1
l Changing of "offsite" circuit to " qualified" circuit appears to be a problem without the carryover of the CTS qualification of "Each units System Auxiliary Transformer bank energized from an independent transmission circuit." The ITS LCO Bases state that a qualified circuit is as defined in the FSAR yet, the discussion then goes on to state in l
( tabular form what the two qualified circuits are. The problem with that discussion is that '
l there is no assurance of the SATs being energized from independent transmission' circuits.
In fact, the iTS 3.8.1 Bases Background states, in part ".. switchyard ara maintained in accordance with the UFSAR and are not (emphasis added) governed by the requirements of
. Technical Specifications." Both the words of the STS and those of the CTS assure that independence will be maintained while the ITS does not. (Note: Qualified circuit has also i
been substituted into other places in the ITS).
3.8.1-9 DOC L2 The DOC states "This backup source of power is not credited in any design basis event and is not needed to preclude any new or different accident." That statement does not adequately explain why, if that is the case, the requirment still ended up in the CTS. Was
! it included for any extended action time or other consideration elsewhere in the CTS?
- l. 3.8.1-10 DOC L3 l' This DOC explains the two relaxations but provides no basis for why either is acceptable.
3.8.1 11 ITS SR 3.8.1.3 Note 1 In the ITS, the use of the manufacturer's recommendations is permissive. However, in CTS 4.8.1.1.2.a.5 the test must be done in accordance with the manufacturer's L recommendations. There is no discussion supporting this less restrictive change.
3.8.1 12 DOC LA6 i
The acceptable load range values (greater than or equal to 4950 KW and less than or equal to 6050 KW) are not consistent with the CTS footnote 6050 (+0, -150) or the values in
'ITS SR 3.8.1.14. The ITS SR values are consistent with the ITS SR Bases which in turn make the Bases inconsistent with LA6. What are the correct numbers?
3.8.1-13 DOC L10 The DOC states "No analyzed event credits the use of the cross connect for DG operation
... " That does not explain why it still ended up in the CTS.
BB2_CR_3.8 2 April 16,1998 L
Byron & Braidwood Improved TS Review Comments ITS Section 3.8, Electrical Power Systems
- 3.8.1 DOC LA10 t
L The DOC states "This capability is not a credited function for any assumed design basis event ..." Again this does not explain why it still ended up in the CTS.
3.8.1 15 DOC L15-Is this change considered less restrictive'because in the CTS loss of power would require a 2 square inch vent while the ITS allows the RHR suction relief or other paths that do not
! ' rely on power to be used? If that is the case, isn't that just letting the LTOP TS control? If so, why isn't this an sdministrative change?
l 3.8.1-16 ITS LCO 3.8.1 and insert 3.8-98 ITS LCO 3.8.1. states the DGs are capable of supplying "the ... System." Insert 3.8 98
, makes ITS LCO 3.8.2 state two DGs capable of supplying "one division of ... subsystems."
l STS LCO 3.8.1 states two DGs " capable of supplying the onsite IE .. subsystems." In
- order to make it clear that each DG supplies subsystems (consistent with the STS and LCO l_ 3.8.2) ITS 3.8.1 should read " two DGs each capable of supplying one division of ... the l Class IE power distribution system."
3.8.1-17 JFD P25 CTS requires the diesel to start from " ambient" and the STS requires from " standby" conditions for SRs 3.8.1.2,11,12,19, and 20. It is correct as stated that as the terms are used, they mean the same. However, using neither term in the'lTS would allow any of the above tests to be run in a situation where the diesel was already at or about full operating temperatures. The STS language should be adopted to ensure that these tests are done only from true standby / ambient conditions.
3.8.1 18- Insert to Bases for ITS SR 3.8.1.16 The bases discussion has been modified to state the SR is in general conformance with the l recommendations of Reg Guide 1.9 paragraph 2.2.11. How is this reflected in the discussion.of Reg Guide 1.9 contained in FSAR Appendix A7 -That discussion doec not appear to contain any qualifications with respect to this testing, j 3.8.1-19 DOC L28 and JFD P22 j identified as Beyond Scope item #11 BB2_CR_3.8 3 April 16,1998 g l
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Byron & Braidwood improved TS Review Comments ITS Section 3.8, Electrical Power Systems
- 3.8.1-20 DOCS L26 and L29, and JFDs P21 and P23 Identified as Beyond Scope item #12 3.8.1-21 DOC L24 and JFD P23 Identified as Beyond Scope item #13 3.8.1-22 JFD P9 This JFD is applicable to LCOs 3.8.2 and 3.8.7, it is unclear why it is used in the markup of STS 3.8.1 (Page 3.8-4).
3.8.1-23 Bases for ITS SR 3.8.1.3 Given that the second paragraph of the Bases says that there are no power factor requirements and that the DG is normally operated between 0 and 1000 kVars, wouldn't it be better to modify the discussion in the last paragraph to remove the power factor discussion or change it to kVars discussion?
lTS 3.8.2 l
i 3.8.2-1 DOC A14 The intent of ITS Conditions A and B should be to return the inoperable battery charger to operable status and once returned to that status break the cross-tie with the other unit and begin to use that charger. As proposed in DOC A14,if the charger could be operable sooner than the required Completion Time the cross-tie would not have to be broken for up ~
to 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />. That may not have been the intent but giving the cross-tie a separate Completion Time certainly makes that reading a reasonable one.
3.8.2-2 JFD C10 Staff has not seen or reviewed changes proposed by WOG-81.
3.8.2-3 JFD P21 and Bases JFD P26 The LCOs and Bases for STSs 3.8.2,3.8.8, and 3.8.10 have been modified by adding a ,
note stating "LCO 3.0.3 is not applicable". If this is a generic issue a generic change l should be proposed for the NRC to consider. On a plant specific basis it is beyond the ]
j scope of the conversion. i l
l 1 i l
BB2_CR_3.8 4 April 16,1998 l
L i
1 Byron & Braidwood improved TS Review Comments ITS Section 3.8, Electrical Power Systems ITS 3.8.3 1
3.8.3 -1 JFD C1 l Staff approval of TSTF-2 Rev 1 is pending.
l l ITS 3.8.4 l
3.8.4-1 ITS 3.8.4 Bases Background in the Background discussion, the word " generally" has been added when discussing conformance with Reg Guide 1.6 and IEEE 308. Byron & Braidwood FSAR Section 8.1 and FSAR Appendix A do not appear to contain any exceptions to either of the standards with j respect to DC electrical power. What requires the insertion of the " generally" qualifier? ,
l 3.8.4-2 Bases JFD P30 in the ITS Bases the phrase "within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />" is deleted. While 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> may not be ;
appropriate for Byron & Braidwood, Sections 5 and 6 of IEEE 308 require that the battery charger time be within a time consistent with the design basis and that the battery charging available. Therefore, the charging time for Byron & Braidwood should be available and should be put in place of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.8.4-3 Insert 3.8.24A
)
1 Why is ITS_ Condition B "that has an inoperable battery charger ..." and Condition C "with !
an inoperable source ..."?
3.8.4-4 ITS SR 3.8.4.7 (Byron only) & JFD P28 and Bases JFD P35 The STS state that a modified discharge test can be substituted for a service test but not with a discharge performance test as specified in the ITS SR. Further, JFD P28 states 1 (quoting IEEE 450) "a modified performance discharge test can 'be used in lieu of a service I test at anytime" This implies that if a performance discharge test can be used (which would be contrary to the STS Bases) it could only be used on some limited basis and not the unlimited basis proposed. Finally, use of the performance discharge test in place of the service test appears contrary to the Reg Guide 1.129 discussion in the Byron & Braidwood 1
. FSAR Appendix A. Further explanation and justification is needed. j 3.8.4 5 ITS 3.8.4 Bases References (Braidwood)
It appears that there should be an additional page following B3.8-58a containing the section references. I h
j BB2_C R.,3.8 5 April 16,1998 '
Byron & Braidwood Improved TS Review Comments j ITS Section 3.8, Electrical Power Systems j l
l l
3.8.4-6 ITS 3.8.4 Bases References (Byron) lEEE 450 -1995 is the version of the standard in the Reference section and is the referenced standard for the discussion of frequency and acceptance criteria for a number of the ITS 3.8.4 (and 3.8.6) SRs. However, the Byron UFSAR states that the frequencies of battery tests are established in accordance with IEEE 450 -1975 (as modified by the
- proposed 1978 revision). Do the references to different version of the standard create any l inconsistencies in application of the SRs and/or are there other instances in which the ITS updates standards from those in the FSAR?
I 3.8.4-7 Bases JFD P18 I STS 3.8.4.6 recommends that specific battery ratings be provided in the SR. However, consistent with CTS SR 4.8.2.1.2.c.4, the wording "a load equal to manufacturer's rating" I' is adopted in the ITS (JFD P16). Consistent with that change, it is proposed that the ITS Bases contain the same wording, if the Bases merely repeat the words of the TS, how is a basis for the TS being provided? Why isn't a specific value (which can be modified n.
accordance with the Bases control program) provided in the Bases?
ITS 3.8.5 3.8.5 1 JFD C9 TSTF 204 has not yet been approved by the NRC.
4 ITS 3.8.6 3.8.6-1 Bases JFD P46 TSTF 203 has not yet been approved by the NRC.
3.8.6-2 DOC L19 The DOC states that ITS SR 3.8.6.3 requires "this same verification ..." when referring to CTS SR 4.8.2.1.2.b.3. However, the CTS requires that the average temperature of all connected cells be checked, while the ITS requires only the average temperature of reoresentative cells be checked. This less restrictive change has not been justified.
ITS 3.8.7 3.8.7-1 JFD P18 and Bases JFD P43 TSTF 202 has not yet been approved by the NRC.
BB2_C R_3.8 6 April 10,1998 l
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l Byron & Braidwood improved TS Review Commonts ITS Section 3.8, Electrical Power Systems ITS 3.8.8 No comments ITS 3.8.9 3.8.9-1 JFD C4' '
How was the editorial comment provided to the NRC.
3.8.9-2 DOC L18 On a generic basis the change proposed here was rejected when the staff considered TSTF 16. If arguing for it on a plant specific basis it is beyond the conversion scope.
ITS 3.8.10 No comments BB2_C R_3.8 7 April 16,1998